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In a reactor core isolation cooling system ("RCIC"), an isolation condenser (IC or iso. condenser; also isolation condenser system) is one of the emergency reactor safety systems in some nuclear plants (boiling water reactor safety systems).
Some reactors, including some BWR/2 and BWR/3 plants, and the (E)SBWR series of reactors, have a passive system called the Isolation Condenser. This is a heat exchanger located above containment in a pool of water open to atmosphere.
In events where the reactor coolant pressure boundary remains intact, the Isolation Condenser System (ICS) is used to remove decay heat from the reactor and transfer it outside containment. The ICS system is a closed loop system that connects the reactor pressure vessel to a heat exchanger located in the upper elevation of the reactor building.
The Isolation cooling system is a defensive system against a condition known as station blackout. This system is not part of the ECCS and does not have a low coolant accident function. For pressurized water reactors, this system acts in the secondary cooling circuit and is called Turbine driven auxiliary feedwater system.
Another example was the Isolation Condenser system, which relied on the principle of hot water/steam rising to bring hot coolant into large heat exchangers located above the reactor in very deep tanks of water, thus accomplishing residual heat removal. Yet another example was the omission of recirculation pumps within the core; these pumps were ...
A project to build a first-of-a-kind small modular nuclear reactor power plant was terminated Wednesday, another blow to the Biden administration's clean energy agenda following cancellations last ...
To cool the reactor, operators resorted to the plant's Emergency core-cooling systems (ECCS), including the isolation condensers, and the High Pressure Coolant Injection systems (HPCI). According to NHK, the isolation condenser system had not been activated in the previous 40 years, and no one present had ever witnessed its operation. [19]
The reactors for Units 1, 2, and 6 were supplied by General Electric, the other three by Toshiba and Hitachi. Unit 1 was a 460 MW boiling water reactor from the BWR-3 design iteration introduced in 1965 and constructed in July 1967.
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